Open Access
Open access
Materials, volume 18, issue 7, pages 1401

Microstructure of CuCrZrV and ODS(Y2O3)-Cu Alloys After Neutron Irradiation at 150, 350, and 450 °C to 2.5 dpa

Michael Klimenkov 1
Carsten Bonnekoh 1
Ute Jaentsch 1
M Rieth 1
Hans-Christian Schneider 2
Dmitry Terentyev 3
Koray Iroc 3, 4
Wouter Van Renterghem 3
1
 
Karlsruhe Institute of Technology (KIT), Institute for Applied Materials—Applied Materials Physics, 76021 Karlsruhe, Germany
2
 
Karlsruhe Institute of Technology (KIT), Institute for Applied Materials—Mechanics of Materials and Interfaces, 76021 Karlsruhe, Germany
4
 
Electron Microscopy for Materials Science, Department of Physics, University of Antwerp, 2000 Antwerp, Belgium
Publication typeJournal Article
Publication date2025-03-21
Journal: Materials
scimago Q2
wos Q2
SJR0.565
CiteScore5.8
Impact factor3.1
ISSN19961944
Abstract

In this study, the results of transmission electron microscopy (TEM) examinations of neutron-irradiated (2.5 dpa at 150 °C, 350 °C, and 450 °C) CuCrZrV and ODS(Y2O3)-Cu alloys are presented. These materials were developed for application as heat sink materials in fusion technology. This study includes TEM imaging and quantitative analysis of neutron radiation-induced defects such as dislocation loops and voids as well as the determination of the conditions for their formation. It was found that dislocation loops of a0½⟨110⟩ type form in both alloys at all irradiation temperatures. The formation of voids in CuCrZrV alloy is effectively suppressed. The neutron irradiation causes a redistribution of Cr, Zr, and V in the CuCrZrV alloy. A particular focus was on the investigation of the distribution of the transmutation products Ni and Zn. Ni tends to segregate at the Cr-rich clusters and forms a shell around them, while Zn is evenly distributed.

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